利用磁诊断推断细长托卡马克等离子体的运行极限

T. Bellizio, R. Albanese, G. Ambrosino, M. Ariola, G. Artaserse, F. Crisanti, V. Coccorese, G. De Tommasi, P. Lomas, F. Maviglia, A. Neto, A. Pironti, F. Rimini, F. Sartori, R. Vitelli, L. Zabeo
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引用次数: 2

摘要

托卡马克是地球上最有希望的核聚变方法。它们是一种环形机器,等离子体在环形容器中加热,并通过外加磁场使其远离容器。为了在托卡马克中实现高性能,需要具有细长极向截面的等离子体。这种细长的等离子体在垂直方向上是不稳定的,因此在快速时间尺度上的位置控制显然是所有机器的基本特征。在这种情况下,等离子体控制升级(PCU)项目旨在提高JET托卡马克的垂直稳定(VS)能力。本文介绍了新型的JET VS系统,重点介绍了如何利用该实时系统的灵活性,在最大可控扰动方面扩大其操作极限。此外,还介绍了最近在JET上进行的实验。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Using magnetic diagnostics to extrapolate operational limits in elongated tokamak plasmas
Tokamaks are the most promising approach for nuclear fusion on earth. They are toroidal machines where the plasma is heated in a ring-shaped vessel and kept away from the vessel by applied magnetic fields. To achieve high performance in tokamaks, plasmas with elongated poloidal cross-section are needed. Such elongated plasmas are vertically unstable, hence position control on a fast time scale is clearly an essential feature of all machines. In this context the Plasma Control Upgrade (PCU) project was aimed at increasing the capabilities of the Vertical Stabilization (VS) of the JET tokamak. This paper introduces the new JET VS system and focuses on how the flexibility of this real-time system has been exploited to enlarge its operational limits in terms of maximum controllable disturbance. Moreover, the experiments recently carried out at JET are presented.
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